ML20154J059
| ML20154J059 | |
| Person / Time | |
|---|---|
| Issue date: | 10/09/1998 |
| From: | Collins T NRC (Affiliation Not Assigned) |
| To: | Holahan G NRC (Affiliation Not Assigned) |
| References | |
| TAC-M91256, NUDOCS 9810150157 | |
| Download: ML20154J059 (1) | |
Text
. . _ _. _ _ . . . _ _ . _ _ _ _._._ _ _ _ . . _ _ . . . - - - _
october 9, 1998
' MEMORANDUM TO: Gary M. Holahan, Director Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation FROM: Timothy E. Collins, Chief /s/ l Reactor Systems Branch l
Division of Systems Safety and Analysis .
l
SUBJECT:
CLOSEOUT OF HIGH-BURNUP FUEL ACTION PLAN '
(TAC NO. M91256) l The High-Bumup Fuel Action Plan was initiated in September 1994 to assess high-burnup fuel j performance and to evaluate the adequacy of SRP licensing acceptance criteria. To date all l but.one of the milestones (21 of 22) has been completed. The remaining milestone is for RES i to respond to the October 4,1993 NRR user needs letter based on the results of the research I programs currently in progress. This research has been included in the Agency Program Plan i for High-Burnup Fuel that was fonvarded to the Commission in a memorandum dated July 6, 1998, from L. J. Callan, Executive Director for Operations. Since the High-Burnup Fuel Action ,
Plan has met its purpose, including issuance of the Agency Program Plan for High-Burnup Fuel I which incorporates the remaining milestone, the High-Burnup Fuel Action Plan is being closed by virtue of this memorandum. The Director's Quarterly Status Report has been updated to reflect closure of the High-Burnup Fuel Action Plan.
CONTACT: S. L. Wu, SRXB/DSSA, 415-3284 blSTRIBUTION: : File' Center GHolahan FAkstulewicz SWu PDR TCollins JConan SRXB R/F KBohrer
/0 DOCUMENT NAME: G:\ACTNHlBU.CLO OFFICE: SRXB:DSSA S .DSSA SRXB: DSS D:
NAME: SWU LJ JL S TCOLLINS 'GHO HAN 03 DATE: 9/ /9 9/16 /9 8 )p/0f/98 9/ /9 OFFICIAL RECORD COP pn JQum y gn UA g M 44J P.?""q g pet h 91)f m
1 P 7 r.1 o 5 981 150157 981009
- @ ( [- S 'h .)
POR ORQ NRRA A' lV PDR -
w.